Dissertation　

About 73 item dissertation in line with TL33,Reactor thermal hydraulics design, calculation query results,the following is 1 to 50(Search took 0.048 seconds)

  1. Numerical Simulation of the Flow and Heat Transfer Characteristics Within Spent Fuel Pool,YeShuiXiang/Harbin Engineering University,0/26
  2. Study on Convection Heat Transfer Characteristics of Pebble-bed with Internal Heat Source,ZhouPing/Harbin Engineering University,0/6
  3. Study of Flow and Heat Transfer in Rectangular Channel in Periodic Force Field,WangChang/Harbin Engineering University,0/18
  4. Research on Resistance and the Transition Characteristics of Pulsating Flow in Narrow Channels,ZhangChuan/Harbin Engineering University,0/15
  5. Natural Circulation Nuclear-thermal Coupling Characteristics Research under Rolling Motion,ZhangLianSheng/Harbin Engineering University,0/44
  6. Experimental Research for Effect of Rolling Motion Upon the Characteristics of Flow Boiling Heat Transfer,LvLuLu/Harbin Engineering University,0/6
  7. Study on Pressure Drop Characteristics of Flow Boiling in Narrow Channel in Rolling Motion,HanDong/Harbin Engineering University,0/10
  8. Chaotic Analysis and Prediction on Flow Instability of Natural Circulation under Rolling Motion Condition,ZhangWenChao/Harbin Engineering University,0/92
  9. Numerical Simulation of Multiphase Pipe Flow,WuJieJie/Xiamen University,0/0
  10. The Research of IPWR’s Thermal-Hydraulic Behavior,LiuJie/Nanhua University,0/2
  11. Research on Simulation for Mixing and Stratification in Large Enclosures,ZhangZuo/North China Electric Power University,0/8
  12. Numerical Simulation of Magnetohydrodynamic Laminar Flow in Duct with Flow Channel Insert,XuTianNeng/Hangzhou University of Electronic Science and Technology,0/23
  13. The Study for18F Dust Transport Characteristic in Reactor Body and Control Rods’ Drive Mechanism Leakage Monitoring System Sampling Tube of PWR,LiChengGuo/Nanhua University,0/33
  14. Thermal Analysis of HTGR Helical Tube Once Through Steam Generator Using Porous Media Method,AoZiYi/Tsinghua University,0/57
  15. The Cavitation Performance Analysis and Assessment of a Mixed Flow Pump Designed with Model Transformation Method,WangYiMing/Dalian University of Technology,0/43
  16. Coupling of Particle Method with Grid Method and Its Application on Solid-Liquid Phase Flow,WangYiPing/North China Electric Power University,0/64
  17. Numerical Simulation of Supercritical Water Thermal-hydraulic Behaviour in4-rod Bundles,HeSiZuo/Shanghai Jiaotong University,0/66
  18. Finite-element Analysis of Fluid Dynamics and Fluid-structure Interaction in Nuclear Valve,ChenHong/Dalian University of Technology,0/91
  19. A Study of Calculation Method for Thermal Performance Correction Curves of Steam Turbine Unit in PWR Nuclear Power Plant,ZhuangDaMing/Zhejiang University,0/120
  20. Study on Transient Nodal Green’s Function Method and Coupled Method with Thermal-Hydraulic,ZhaoWenBo/Tsinghua University,1/88
  21. Research on a Novel Capacitance Sensor for Measuring Wetness of Flowing Wet Steam,NingDeLiang/Harbin Engineering University,4/505
  22. Thermal Analysis of Nuclear Reactors,A.A.MuFuDaHe/Zhejiang University,0/326
  23. Investigation of Direct Contact Condensation of Saturated Steam on Free Subcooled Liquid,LiZuoNing/Chongqing University,2/353
  24. Research on the Hydraulic Characteristics in the Density Lock,GuHaiFeng/Harbin Engineering University,1/41
  25. Study on Water Level Control System of Steam Generator Based on FCS,ZhangBing/Harbin Engineering University,1/225
  26. Application of Reliability Analysis Based on Multilevel Flow Models in Nuclear Power Plant,ZhanJing/Harbin Engineering University,1/144
  27. Swing bubble departure point for the natural circulation in rats,QinShengJie/Harbin Engineering University,2/101
  28. Water vapor condensation heat transfer in a vertical tube experimental study,SuiHaiMing/Harbin Engineering University,3/347
  29. Heat Transfer Analysis and Regression Evaluation of Fluids at Supercritical Pressures in Vertical Upward Ducts,ZhangYaQi/Shanghai Jiaotong University,1/268
  30. The Numerical Study on Heat Transfer and Flow Friction of Single-phase Convection in Rectangular Narrow Channel,LiLei/Harbin Engineering University,0/217
  31. Fault Diagnosis Expert System Study Based on Artificial Neural Network for the Condensation Equipment,ZhangXiuChun/Harbin Engineering University,2/270
  32. China Experimental Fast Reactor air heat exchanger thermal fluid dynamics research,LiJing/China Institute of Atomic Energy,0/122
  33. Fast Reactor single box fuel assembly coolant flow field temperature field study,LiuYiZhe/China Institute of Atomic Energy,0/192
  34. Dry -type critical phenomena prediction model research,ZhangZhenXing/China Institute of Atomic Energy,0/35
  35. ADS liquid target system flow visualization experimental study and numerical simulation analysis,XuChangJiang/China Institute of Atomic Energy,0/111
  36. China Experimental Fast Reactor core export area temperature distribution,XueXiuLi/China Institute of Atomic Energy,2/136
  37. Research of Initial Point of Net Vapor Generation in Natural Circulation at Annular Channel,YuWenChi/Harbin Engineering University,0/108
  38. CARR core three-dimensional flow field and temperature field numerical simulation,YangChangJiang/China Institute of Atomic Energy,1/262
  39. Hospital neutron irradiation thermal-hydraulic numerical simulation,MaoYuLong/China Institute of Atomic Energy,0/37
  40. China Experimental Fast Reactor the sodium pool three-dimensional thermal-hydraulic analysis,XuYiJun/China Institute of Atomic Energy,3/301
  41. Dry test tube upward mobility study,ZouLing/China Institute of Atomic Energy,3/81
  42. Study about Thermal Hydraulic Static Characteristics Calculation of Nuclear Steam Generator,YaoYanGui/Shanghai Jiaotong University,5/967
  43. Investigation of Temperature Distribution and Numerical Simulation of Heat Exchanging of Uniform Inner Heat Source Liquid in Column-form Liquid Pool,DongZuo/Chongqing University,0/110
  44. TACR Core Steady-State Thermal and Hydraulic Design,YouSongBo/Tsinghua University,1/292
  45. RELAP5/MOD3 coupled with THAS-PC4 Research Program,WangJun/China Institute of Atomic Energy,0/333
  46. Investigation of Direct Contact Condensation of Saturated Steam on Sub Cooled Liquid and 2-dimensional Temperature Distribution,ZhaoJianGang/Chongqing University,0/153
  47. Investigation of Condensation of Steam in the Presence of Noncondensable Gases,YuanShiPing/China Institute of Atomic Energy,2/383
  48. Simplified model of the fluid in the reservoir fluid container seismic calculation kinds of applications and three-dimensional fluid-structure interaction program development,GaoXiaoAn/China Institute of Atomic Energy,1/294
  49. Development of Numerical Simulation Software for the Flow-Structure Interaction of the Plate Fuel Assembly in an Advanced Reactor,ZhangJuanHua/North China Electric Power University (Beijing),0/192
  50. Research on Designing the Outlet Nozzle in Main Vessel of Supercritical Water Reactor,YangLinMin/North China Electric Power University (Beijing),0/104

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